ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Kenneth L. Ferguson
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 5-12
Technical Paper | Reactor | doi.org/10.13182/NT79-A32157
Articles are hosted by Taylor and Francis Online.
Radioactive effluents and concentrations expected from the Clinch River Breeder Reactor (CRBR) during normal operation have been assessed. Developed were the individual off-site dose values as well as population doses within an 80-km (50-mile) radius of the proposed facility. Comparison has been with the as low as reasonably achievable (ALARA) exposure objective as in 10CFR50, Appendix I, of the Code of Federal Regulations. All estimated releases are well within the concentration limits found in 10CFR20. The calculated doses to individuals are consistently lower than values of 10CFR50, Appendix I. Population exposures are a very small fraction of that due to background radiation. Exposures due to CRBR effluents are also in conformity with cost-benefit arguments of the ALARA objective. Measures are in place to follow the design progression and operation of the facility to retain the ALARA aspect of the doses associated with the effluent releases.
